ML17059A740
| ML17059A740 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/20/1995 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A741 | List: |
| References | |
| NUDOCS 9503270067 | |
| Download: ML17059A740 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1
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MENDMENT TO F CI ITY OP ING LICENSE Amendment No. 154 License No. DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated June 30,
- 1994, as supplemented March 7,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.'he issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is'amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
95032700b7 950320 PDR
'ADQCK 05000220
'P PDR
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 154, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 20, 1995 Ledyard B. Marsh, Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT AM NDMENT NO. 154 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa e
117 Insert Pa e
117
TABLE3.2 7.1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATIONVALVE
~Setem 1.
Core Spray System 2.
Condensate Supply to Core Spray (Keep Fill System) 3.
Core Spray Supply to Shutdown Cooling (Waterseal)
Valve No.
40-03 40-13 40-20 40-21 40-22 40-23 38-165 38-166 38-167 38-168 38-169 38-170 38-171 38-172 Maximum(a>> Aiiowabfe Leaka e
55.0 gpm
<5.0 gpm c5.0 gpm
<5.0 gpm s5.0 gpm s5.0 gpm
<0.375 gpm a0.375 gpm
<0.375 gpm a0.375 gpm s0.375 gprn w0.375 gpm w0.375 gpm
<0.375 gpm
~Footoo e:
(a)
- 1. Leakage rates shall be limited to 0.5 gpm per nominal inch of valve diameter up to a maximum of 5 gpm.
- 2. Test differential pressure shall not be less than 150 psid.
- 3. The observed leakage at test differential pressure shall be adjusted to the functional maximum pressure differential.
AMENDMENTNO. gg$
154